Aquafluor process

A more radical modification of the Purex process, the Aquafluor process, developed by General Electric for its Midwest Fuel Recovery Plant, retained only a single TBP co-decontamina-tion cycle followed by a continuous anion exchange contactor in which plutonium was to be removed from the U-Pu nitrate solution. The performance of this plant was never tested with plutonium, since General Electric decided to forego operation of the plant after technical difficulties developed during the "cold" checkout trials. 

In the Aquafluor process [G4] developed by the General Electric Company, most of the plutonium and fission products in irradiated light-water reactor (LWR) fuel are separated from uranium by aqueous solvent extraction and anion exchange. Final uranium separation and purification is by conversion of impure uranyl nitrate to UFg, followed by removal of small amounts of PuF , NpFg, and other volatile fluorides by adsorption on beds of NaF and Mgp2 and a final fractional distillation. A plant to process 1 MT/day of irradiated low-enriched uranium fuel was built at Morris, Illinois, but was never used for irradiated fuel because of inability to maintain on-stream, continuous operation even in runs on unirradiated fuel. The difficulties at the Morris plant are considered more the fault of design details than inherent in the process. They are attributed to the attempt to carry out aqueous primary decontamination, denitration, fluorination, and distillation of intensely radioactive materials in a close-coupled, continuous process, without adequate surge capacity between the different steps and without sufficient spare, readily maintainable equipment [G5, R8]. 

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